Sputter deposition and plasma modification of tungsten alloys for nuclear fusion applications

dc.contributor.authorMahoney, Nicholas
dc.date.accessioned2025-05-13T05:55:19Z
dc.date.available2025-05-13T05:55:19Z
dc.date.issued2025
dc.description.abstractThe ITER reactor aims to be first thermonuclear fusion device to demonstrate net fusion power. Critical plasma-facing components in the reactor will be made of tungsten, but helium plasma irradiation is known to embrittle tungsten metal. A future reactor will therefore need an alternative material to extend the lifetime of the components. This thesis investigated the use of tungsten alloy films as a plasma-facing material for a future reactor. Tantalum and chromium were chosen as the alloying elements, and 60 − 100 nm films were manufactured using magnetron sputter deposition at a variety of alloy concentrations. Tungsten alloy films are known to deposit in an undesirable A15 crystal phase. The films were heat treated at 650◦C for 1 hour, 2 hours and 4 hours to induce and investigate the phase transition from A15 to BCC structure. X-ray diffraction patterns confirmed the presence of an A15 structure prior to annealing. The A15 phase was very stable in comparison with past results, requiring over 2 hours at 650◦C to transition to BCC. This was speculated to be linked to oxygen trapped in the films during deposition. The phase transition was slower in alloyed films than a pure tungsten control, with the retarding effect of tantalum stronger than chromium, which suggested the alloying atoms further stabilised the deposited A15 structure. Resistivity of the films saw a reduction with annealing time characteristic of the phase transition. The annealed alloy films were then exposed to helium plasma in the Magnetised Plasma Interaction Experiment at 300◦C, 500◦C and 800◦C. Surface morphology changes were tracked with secondary electron imaging. At 800◦C, surface pits were seen, which were larger in a pure tungsten film than in low concentration alloy films. Advanced surface roughening was observed in the chromium films, while a high concentration tantalum film had no surface damage at all. X-ray diffraction patterns confirmed these trends, and showed an increase in microstrain with the surface roughening in the chromium alloys. These results suggest W-Ta alloy films may have superior irradiation resistance than W-Cr alloy films, but more work is needed to confirm the trends in alloy concentration.
dc.identifier.urihttps://hdl.handle.net/1885/733750337
dc.subjectNuclear Fusion
dc.subjectITER
dc.titleSputter deposition and plasma modification of tungsten alloys for nuclear fusion applications
dc.typeThesis (Honours)
dcterms.valid2024
local.contributor.affiliationResearch School of Physics, College of Science, The Australian National University
local.contributor.supervisorCorr, Cormac
local.identifier.doi10.25911/7TC3-N437
local.identifier.proquestYes
local.mintdoimint
local.type.degreeOther

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